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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld ML18016A8891999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML18009A6581990-09-11011 September 1990 Submits Addl Info Re Use of Hafnium Control Rods at Facility.All Rods Will Be Removed During Spring 1991 Outage ML20059H4181990-09-0606 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-13.Corrective Action:Changes to EST-717 in Area of Power Normalization Under Study for Past Several Months ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty ML20059D3511990-08-30030 August 1990 Forwards Decommissioning Financial Assurance Certification Rept Submitted by North Carolina Eastern Municipal Power Agency ML18009A6261990-08-10010 August 1990 Informs That Action Committed to in Response to Generic Ltr 88-14, Instrument Air Supply Sys, Completed ML18009A6241990-08-0303 August 1990 Forwards Addl Info Re Operator Action Times Assumed in Steam Generator Tube Rupture Analyses for Plant,Per 900712 Telcon ML18009A6081990-07-31031 July 1990 Forwards Plan for Shearon Harris Nuclear Power Plant Emergency Exercise - 900919, Per NRC Request.W/O Encl ML20055J4171990-07-30030 July 1990 Forwards Rev 5 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices ML18009A5991990-07-0606 July 1990 Comments on Electrical Distribution Sys Functional Insp Rept 50-400/90-200 on 900212-0316.Seismic Qualification Package Subsequently Upgraded to Include Qualification Info Based on Receipt of Part 21 from Transamerica Delaval ML18009A5851990-06-28028 June 1990 Advises That Emergency Preparedness Exercise Scheduled on 900919.Exercise Will Consist of Simulated Accident at Plant Site & Will Involve Planned Response Actions.Objectives to Be Fulfilled Encl ML18009A5621990-05-30030 May 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Rept 50-400/90-06.Corrective Actions:Procedures OST-1008 & OST-1108 Revised to Delete Stroke Testing of Valve 1ST-359 on Quarterly Basis ML18009A5141990-05-0303 May 1990 Forwards Eddy Current Exam CP&L Shearon Harris Nuclear Power Plant Steam Generators A,B & C, Providing Results of Inservice Insps Performed During Plant Second Refueling Outage in Oct 1989 ML18009A4941990-04-26026 April 1990 Forwards Radiological Environ Operating Rept,1989, Radiological Environ Operating Rept,Vol II,Jan-June 1989, Sample Analyses Data & Radiological Environ Operating Rept,Vol III,Jul-Dec 1989,Sample Analyses Data. ML18009A5031990-04-25025 April 1990 Submits Suppl 2 to Relief Request R2-001 Re Plant 10-yr Inservice Insp Plan,Per 880129 Request ML18009A4911990-04-24024 April 1990 Forwards Addl Info Re Proposed Wakesouth Regional Airport to Be Located Near Facility,Per 900411 Request.Info Previously Provided to NRC During 900320 & 23 Telcons ML18009A4841990-04-24024 April 1990 Forwards Corrected Bases marked-up Page to 900226 Tech Spec Change Request Re Surveillance Intervals ML18009A4251990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Based on Guidelines Provided in NUMARC 87-00, Guidelines & Technical Bases for NUMARC Initiatives.... No Changes to Previous Calculations Necessary & One Deviation Noted ML18009A4231990-03-29029 March 1990 Suppls Response to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Actions:Surveys Performed to Determined Extent & Level of Contamination & Personnel Involved Decontaminated ML18009A4111990-03-23023 March 1990 Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-400/90-02.Corrective Actions:Personnel Involved W/ Quadrant Power Tilt Ratio Calculations & Operability Determination Counseled ML18009A4121990-03-23023 March 1990 Forwards Rev 17 to PLP-201, Emergency Plan & Fission Product Barrier Analysis.Rev to Emergency Plan Incorporates Comments Received During Recent Licensed Operator Requalification Training in Emergency Plan Procedures ML18009A4151990-03-22022 March 1990 Responds to NRC SALP Rept for Jul 1988 - Nov 1989.Contrary to Statement in Rept Significant Amount of Refresher Training Was Conducted During SALP Assessment Period Including Termination & Splicing & Motor & Bus Relays ML18009A4081990-03-19019 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-400/90-01.Corrective Actions:All Calibr Required by Tech Specs for Power Range Nuclear Instrumentation Satisfactorily Completed ML18022A7891990-03-0909 March 1990 Forwards Vols 1 & 2 of Inservice Insp Summary 1st Interval 1st Period,2nd Refueling Outage Completed 891222. ML18022A7881990-03-0606 March 1990 Confirms Understanding of Status of NRC Activities Re Proposed Wakesouth Regional Airport Located Near Plant Site. Pending Issues Should Be Resolved by 900331 to Enable Util to Complete Negotiations W/Airport Authority ML18022A7851990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-400/89-34.Corrective Actions:Valve SI-332 Closed & Gravity Drain Path Isolated & Shift Foreman Required to Review MMM-012 Re Priority/Emergency Maint Work Control ML18022A7721990-02-26026 February 1990 Forwards Application for Amend to License NPF-63,revising Tech Spec Surveillance 4.0.2 to Permit Surveillances to Be Extended Up to 25% of Specified Interval & Removing 3.25 Limitation from Spec,Per Generic Ltr 89-14 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML18022A7701990-02-14014 February 1990 Notifies of Issuance of Renewal of NPDES Permit for Plant. Permit Encl ML18009A3831990-02-0909 February 1990 Responds to 900112 Ltr Re Violation Noted in Insp Rept 50-400/89-35.Corrective Actions:Valves ICS-775 & ICS-776 Added to Inservice Insp Program for Back Seat & Full Flow Testing & ICS-525 Revised to Satisfy Tech Spec Requirements ML18009A3751990-02-0101 February 1990 Forwards Retyped Tech Spec Pages Re 890630 Application for Amend to License NPF-63 Concerning RCS Pressure Temp Limits ML18009A3701990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 IR 05000400/19890281990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 ML18009A3631990-01-26026 January 1990 Responds to NRC Bulletin 88-008, Thermal Stratification in Piping Connected to Rcs. Design Differences That Either Minimize Potential of Occurrence or Enhance Possibility of Detection Should Scenario Be Created at Plant Determined ML18009A3531990-01-25025 January 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence ML18009A3501990-01-22022 January 1990 Forwards Revised Tech Spec Table 3.7-6, Area Temp Monitoring, Per 891218 Tech Spec Amend Request ML18022A7591990-01-17017 January 1990 Submits Results of Aircraft Hazards Study Associated W/ Proposed Wakesouth Regional Airport & Facility ML20005G5731990-01-16016 January 1990 Forwards Response to Insp Rept 50-400/89-32.Encl Withheld (Ref 10CFR73.21) ML18009A3351990-01-0505 January 1990 Forwards Rev 16 to Vol 1,Part 2 of Plant Operating Manual PLP-201, Emergency Plan. Revised NUREG-0654 Comparison W/ Plant Emergency Action Level Flow Path Also Encl for Review ML18009A3171989-12-21021 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-21.Corrective Actions:Incident Reviewed by Both Plant & Nuclear Engineering Dept Personnel to Avoid Future Miscommunication ML18009A3181989-12-15015 December 1989 Forwards Retyped Amend Bar Pages to Tech Spec Table 3.3-3 Re Auxiliary Feedwater Manual Initiation,Per 891026 Application for Amend to License NPF-63 ML18009A3011989-12-15015 December 1989 Forwards Proprietary WCAP-12403 & Nonproprietary WCAP-12404, LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant. WCAP-12403 Withheld (Ref 10CFR2.790(b)(4)) ML18022A7371989-12-13013 December 1989 Forwards Change 3 to Rev 2 to State of Nc Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Incorporating Administrative Enhancements. W/One Oversize Encl ML18009A2971989-12-0808 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Action:Min of Four Decontamination Personnel Will Be Assigned 24 H Per Day During Fuel/Cask Handling to Maintain Cleanliness in Fuel Handling Bldg ML18009A2841989-11-30030 November 1989 Forwards Rev 0 to Core Operating Limits Rept in Support of Cycle 3 Operations ML18005B1531989-11-27027 November 1989 Forwards Retyped Amend Bar Pages to 890630 Request for Rev to License NPF-63 Re RCS pressure-temp Limits ML18022A7311989-11-27027 November 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. ML18005B1511989-11-17017 November 1989 Forwards 15-day Special Rept Identifying Number of Steam Generator Tubes Plugged During Current Inservice Insp Period ML18005B1501989-11-13013 November 1989 Suppls 890403 Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Addl Nontraceable Molded Case Circuit Breakers (MCCB) & MCCBs Traceable to Refurbishers Noted During Records Review 1990-09-06
[Table view] |
Text
~~, -.r
~ . REGULATOR) INFORMATION DISTRIBUTION S TEM (RIDS)
ACCCSSION NBR;8408020042 DOC DATE: 84/07/05 NOTARIZED; NO 'DOCKET Harris Nuclear Power Planti Unit ii Carolina'5000400
~
Shearon 0'ACIL:50-,400 AUTH, NAME AUTHOR AFPILI )TION R
>JATSON g R ~ A ~ Carolina Power 8 Light Co.
REC IP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ Rr Office of Nuclear Reactor Regulationi Director SUBJECT; Forwards info in response to Eddleman Contention 9 re environ qualification program,FSAR wil-l be amended to provide description of program.
DISTRIBUTION CODE: A048S COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR/Licensing Submittal: E'quipment Qualification NOTES:
'DRECIPIENT CODE/NAME COPIES LTTR ENCL RECIPIENT ID CODE/NAME COPIES LTTR ENCL NRR LB3 BC 12 '1 0 BUCKLEYiB 01 1 INTERNALS ADM~LFMB GC NRR KARSCHzR 13 1
1 0
1 1
IE FILE'9 ELD/HDS1 NRR/DE/EQB 12 07 1
1 2
1 1
2 NRR/DL DIR ie 1 1 0 AB 06 1 1 NRR/DS1/AEB 1 1 REG FIL 04 1 1 RGN2 1 1 EXTERNAL: ACRS 15 8 8 LPDR 03 NRC PDR 02 1 1 NSIC 05 NTIS 31 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 24
0 e
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C "I II 1
I 0
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II fl
CIPQ 0 Carolina Power & Light Company SERIAL: NLS-84-343 JUL R5 i9SC Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-400 ENVIRORlENTAL QUALIFICATION PROGRAM
Dear Mr. Denton:
Carolina Power & Light Company hereby provides information in response to Eddleman Contention 9. This information is based on the Shearon Harris Environmental Qualification program. We w111 amend the Final Safety Analysis Report shortly to provide a complete description of our program.
Should you have any questions with regard to this issue, please contact Mr. Sherwood R. Z1mmerman at (919) 836-6242.
Yours very truly, R. A. Watson Vice President Harris Nuclear Project PS/cfr (408PSA)
Cct Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. Bob Legrange (NRC-NRC/EQ) Mr. John D. Runkle Mr. Armand Masciantonio (NRC-NRR/EQ) Dr. Richard D. Wilson Mr. G. F. Maxwell (NRC-SHNPP) Mr. G. 0. Br1ght (ASLB)
Mr. J. P. O'Reilly (NRC-RII) Dr. J. H. Carpenter (ASLB)
Mr. Trav1s Payne (KUDZU) Mr. J. L. Kelley (ASLB)
Mr. Daniel F. Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library 84OBOaOO > i 5ooo40o pDR ADo pDR
- 411 Fayettevitte Street ~ P. O. Box 1551 ~ Raleigh, N. C. 27602
~ ~
SHEARON HARRIS NUCLEAR POWER PLANT ATOMIC SAFETY AND LICENSING BOARD EDDLEMAN CONTENTION NO. 9 9A. The proposed resolution and vendor 's modification for ITT-Barton transmitters has not been shown to be adequate. (Ref. IE Information Notices 81-29, 82-52, and 83-72).
Res onse to Contention 9A:
ITT Barton transmitters, model numbers 763 and 764, are supplied to the Shearon Harris project by Westinghouse.
Carolina Power & Light Company (CP&L) has addressed IE Information Notices 81-29, 82-59, and 83-72 as follows:
Information Notice 81-29 dated September 24, 1981, Equipment Qualification Notice No. 2 Test Summary Report No. 1 indicated noisy output followed by erroneous output for two DP transmitters and noise followed by erroneous output for 40 minutes for one pressure transmitter (Model 763 and 764 ITT Barton). CP&L did not take any action at that time because the manufacturer was investigating the failures, concentrating on aging methodology, test set-up, and duplicating test conditions to establish what the failure mechanisms were. There were no corrective actions recommended at that time. Subsequently, as described in IE Notice 82-52, the causes of the problems were identified and corrected. The transmitters have been successfully retested.
2~ Information Notice 82-52 dated December 21,. 1982, Equipment Qualification Notice No. 2 Test Summary Report No. 2 indicated that the failure mechanisms had been determined to be bad connections in the connector assembly. Satisfactory resolution of the failures on Information Notice 81-29 also had been established. The transmitter was successfully retested by Westinghouse.
CP&L sent all Barton Models 763 and 764 safety-related transmitters back to ITT Barton on November 11, 1982 after receipt of a change notice from Westinghouse for rework (i.e., resoldering connector assemblies). They are still at the factory.
3~ Information Notice 83-72 dated October 28, 1983, Equipment Qualification Notice No. 20 Test Summary Report No. 1 indicated a negative shift in output during initial exposure to operating pressure for the Model 763 pressure transmitter.
The reported defect had a specific cause which was determined to be creep in the mechanical linkage and the material used to attach the link wire to the bourdon tube and strain-sensing beam.
Since the Model 763 Barton transmitters had already been sent to the factory for rework per Information Notices 81-29 and 82-52, CP&L indicated that the 763 transmitters should remain at ITT Barton until all corrective hardware modifications could be implemented at the same (401PSA/ccc)
I time. Westinghouse has maintained a close follow on the Barton transmitter testing and will inform CP&L when qualification testing and developments have been thoroughly evaluated. CP&L will perform an evaluation of the corrective actions to insure that this problem has been corrected, and the results of the evaluation will be documented in the EQ package.
Suppressed zero transmitters are used to measure pressurizer pressure.
The effect of this drift allowance on over-temperature delta T is minimal and can be absorbed. The effect on low trips and DNB calculations is conservative. Credit is taken for the high trip on loss of load only and this transient is not limiting for DNB or overpressure protection.
Therefore, Westinghouse has established that the observed excessive negative drift is not a safety concern.
4~ Information Notice 83-72 dated October 28, 1983, Equipment Qualification Notice No. 23 Test Summary Report No. 1 indicated that the Models 763 and 764 transmitters had thermal nonrepeatability which caused results in performance outside Barton's specification.
The defect was determined to be leakage current through the shafts of the zero and span potentiometers to the mounting bracket.
As stated before for the Model 763 transmitters, CP&L has indicated that the Model 764 transmitters which have already been sent to ITT Barton for rework per IN 81-29 and IN 82-52 should remain at the factory until all hardware modifications can be implemented at the same time. Westinghouse will maintain a close follow on the Barton transmitter testing and will keep CP&L informed of qualification testing and developments until they have been thoroughly evaluated. CP&L will perform an evaluation of the corrective actions to insure that this problem has been corrected and the results of the evaluation will be included in the EQ package.
CP&L believes that the above corrective actions are adequate to address the concerns expressed in Eddleman Contention 9A.
(401PSA/ccc)
9B. There is not sufficient assurance that the concerns with Limitorque valve operators identified in IE Information Notice 83-72 (except for Items C2, C5, and C7) have been adequately resolved.
Res onse to Contention 9B:
The Information Notice 83-72 (IN 83-72) addressed several concerns with the Limitorque valve operators at the Midland Plant. These concerns were related to:
- 1. Terminal blocks underrated, unqualified, unidentifiable (A, B, C9).
- 2. Motor insulation material ambient temperature rating (Cl).
- 3. Orientation of the operators (C3) ~
- 4. Drain plug installation (C4).
- 5. Installed equipment not in accordance with the purchase order and EQ program (C6).
- 6. 0-ring qualification uncertain (C8).
Limitorque Corporation has been contacted on several occasions and has provided several written responses to CP&L concerning the above deficiencies. Limitorque concluded that except for the nylon terminal blocks, the above deficiencies were related to lack of information at Midland and thus do not represent actual equipment qualification concerns applicable to Shearon Harris.
However, it is CP&L's practice to perform an independent assessment of the applicability of IE Notices and Bulletins to Shearon Harris. To that end, the following assessment is offered:
- 1. Terminal blocks will be field verified on a sample basis using vendor supplied information. The verifier will measure the dimensions of the power and nonpower lead terminal blocks, including the point-to-point distances of the terminal screws, using manufacturer catalog information provided by Limitorque. This field verification will ensure that the terminal blocks provided are the same type that were qualified. If any discrepancies are found, inspected.
~ remaining safety-related operators will be
- 2. Motor insulation material is presently being verified in the field as part of our equipment qualification effort. Verification consists of identification of motor insulation class from the motor nameplate data.
For valve operators inside containment insulation class should be RH. If any operators are found not to have RH insulation, Limitorque will be contacted for resolution. No discrepancies have been noted thus far in the verification process.
- 3. Orientation of the operators is specified on design drawings and is independently verified by the on-site Quality Assurance (QA) organization. (See our response to Eddleman 9E of this submittal.)
(401PSA/ccc)
- 4. Drain plugs are required by the vendor for inside-containment operators. Installation is inspected by site QA and verified on a sample basis by the site EQ group.
- 5. Safety-related equipment is manufactured under the vendor's facility QA program. Prior to shipment, CP&L, Westinghouse, or Ebasco inspect (both
'documentation and physical) the equipment and issue a "Quality Release". Upon arrival on site, CP&L QA personnel inspect the equipment prior to release to the field for installation. Thus, the installed equipment is assured to be in accordance with the purchase order and EQ program.
- 6. 0-rings are designed for the specific application and are qualified as an integral part of the operator assembly.
Limitorque EQ reports have been reviewed by Westinghouse, Ebasco, and CP&L and have been found to be qualified. Except for the above mentioned verifications; no further action is deemed necessary at this time.
(401PSA/ccc)
9C. It has not been demonstrated that the RTDs have been qualified in that the Arrhenius thermal aging methodology employed is not adequate to reflect the actual effects of exposures to temperatures of normal operation and accidents over the times the RTDs could be exposed to those temperatures. (Ref. NUREG/CR-1466, SAND-79-1561, Predicting Life Expectancy of Complex Equipment Using Accelerated Aging Techniques.)
Res onse to Contention 9C:
Depending on the application of a piece of equipment, the environment it is exposed to can vary. The Shearon Harris Environmental Qualification Program includes Aging, which reflects the intended application. The goal of the aging program is to simulate a certain age of the equipment (40 years) prior to testing under the severe environmental conditions representative of the postulated accident to which it must be qualified.
The aging program addresses the types of experiments discussed in Part II of NUREG/CR-1466 (SAND 79-1561) "Predicting Life Expectancy and Simulating Age of Complex Equipment Using Accelerated Aging Techniques",
- 1. Failure Mode Tests,
- 2. Capability Tests, and
- 3. Accelerated Aging Tests, as follows:
- 1. Failure Mode Tests The purpose is to indicate where a change in material, components, or design may lead to enhanced reliability. This is accomplished by exposing the equipment to environments that have higher than use stress levels. With respect to environmental qualification at Shearon Harris, the equipment is subjected to an aging temperature greater than the actual environment temperature it will be subjected to during its installation. All components making up the equipment see this higher temperature, which places the equipment in a high stress condition for a specific period of time usually expressed in many hours, or days.
- 2. Compatibility Tests The purpose is to show whether the aging of a specified material is affected by the aging of other materials in the group. As stated in the Failure Mode Tests, all components making up the equipment are aged simultaneously under high stress conditions thus accounting for this condition.
- 3. Accelerated Aging Tests This is the method employed to age the equipment. Specifically, aging is primarily based on the Arrhenius methodology which is acceptable to the NRC (See NUREG 0588, Section 4-4).
On the Shearon Harris RTDs, CP&L has reviewed the Westinghouse supplied test results and has done a detailed analysis of the results. This analysis included a review of the aging parameters used by Westinghouse with comparison to actual parameters values at Shearon Harris.
Additional information about aging methodology used for the Harris RTDs is presented in WCAP-8587, which has been approved by the NRC.
(401PSA/ccc)
As reported in WCAP 8687, Supplement 2 E-05A and E-06A, organic materials in the RTD assemblies are limited to epoxy potting at the cable/probe interface and silicon varnish on the cable lead. With the sealed armor protecting the RTD cable from the intrusion of moisture, the silicon varnish does not serve a critical function. Only the epoxy serves any physical function in providing some support for wires in the transition from cable to probe body.. Like the varnish, the potting is not a primary seal against moisture in the event of a Design Basis Event. The other materials are inorganic and are not age-sensitive.
The accelerated aging parameters were chosen for an ambient temperature of 50'C with an elevated temperature in the area of the epoxy potting of 50'C above ambient. The elevation of temperature above ambient is the result of heat transfer from the reactor coolant pipe or reactor coolant bypass manifold. Because no age-sensitive material is exposed to the full reactor coolant temperature, there is no reason to perform accelerated aging simulation using that temperature over the intended qualified life. The accelerated thermal aging is described in the respective EQ test reports which have been approved by the NRC.
(401PSA/ccc)
9D. The qualification of instrument cables did not include adequate consideration and analysis of leakage currents resulting from the radiation environment. These leakage currents could cause degradation of signal quality and/or spurious signals in Harris instrument cables.
Res onse to Contention 9D:
In addressing to the claim that the qualification of instrument cables did not include adequate monitoring of leakage currents during and after tests, it merits noting that IEEE 383-1974, which forms the basis for the cable qualification program at Shearon Harris, does not required monitoring this parameter.
A review of the methods used in testing cable for Shearon Harris will, however, show that even though leakage current is not a standard measured parameter, other tests that are performed are equal or even haxsher than leakage current measurements. One of these tests is the post thermal/radiation test which involves submergence of the aged cable and application of high voltages. After cables have been aged thermally and received an equivalent 40 year plus accident total integrated radiation dose, they are straightened and recoiled with an inside diameter if approximately 20 times the cable overall diameter and immersed in tap water at room temperature. While still immersed these specimens should pass a voltage withstand test at voltages several times higher than required during normal operation. If an insulation breakdown has occurred during the test, this would show up.
Additionally, in the case of instrument cable where leakage current is a concern, insulation resistance, which can be used to indicate the values of
, leakage current, is also frequently measured before, during, and after the environmental qualification. A comparison of pre-test to post-test values of
.insulation resistance is done during the test report reviews.
All of the above tests results are reviewed by CP&L and this review is part of the test report review packages.
(401PSA/ccc)
t 9E. There is not sufficient assurance that the physical orientation of equipment in testing is the same as the physical orientation of equipment installed.
Res onse to Contention 9E:
The environmental qualification reports describe and in some cases even provide photographs of the listed equipment orientation/set-up during their testing. The test set-up is reviewed in detail by the design organization with particular attention paid to any limiting conditions. The vendor may test in several orientations, test in the most limiting orientation, test in a single orientation and then analyze other orientations, or simply specify the exact tested orientation. This is also carefully reviewed by the design organization. The results of these reviews are then fed back into the installation drawings and form the basis for field installation. Any orientation questions, discrepancies, or inconsistencies are resolved with the vendor.
CP&L then assures that the equipment is installed per design drawings.
Contractor personnel use only controlled engineering documents to install equipment. A very large quality inspection organization as'sures installation per design through a comprehensive, independent field inspection program using these design documents. Installation problems identified by the field installation personnel are resolved by design engineering personnel during the installation process. Documentation is maintained as part of plant records justifying the changes, thus allowing for future audit and verification.
Problems that are identified during the inspection process are also evaluated by design engineering personnel. The non-conforming item is either reworked or justified by design engineering to be acceptable as-is.
Thus, it is shown that this multi-faceted program involving the vendor, design engineering, construction installation personnel, and quality inspection organization ensures that qualified equipment is installed in an orientation consistent with the test program. It should also be noted that in addition to the above, there are various walkdown programs being developed (post installation, post inspection) which will provide an additional overlay of assurance on the installation process.
(401PSA/ccc)
1 9F. The effects of radiation on lubricants and seals has not been adequately addressed in the environmental qualification program.
Res onse to Contention 9F:
The Shearon Harris harsh environment qualification program uses actual type tests to demonstrate qualification. This includes irradiation of equipment as a whole, including the seals, lubricants, etc., used in the equipment. As such, the effects of radiation on lubricants and seals are included in the qualification of the equipment using these elements. This is documented in the Equipment Qualification packages and is reviewed by CP&L and audited by NRC. In those cases where lubricants, seals, etc., are the limiting component, inspection and replacement requirements are specifically hi-lighted by the EQ program and transmitted to operations personnel for inclusion in the maintenance and surveillance program for the plant.
(401PSA/ccc)
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- 90. There is inadequate assurance that failure to report all results of environmental qualification tests, including failures, has been brought to light in connection with electrical equipment installed in Harris.
This includes past test failures of equipment which subsequently passes an EQ test and test failures of equipment which is said to be qualified by similarity. (Ref. Item 2, Page 5, L. D. Bustard et al., Annual Report: Equipment Qualification Inspection Program, Sandia National Laboratories, FY83.)
Res onse to Contention 9G:
Environmentally qualified Class 1E electrical components are purchased from vendors who have CP&L approved quality assurance programs. The Vendor Surveillance Unit verifies that the vendor QA program and implementation are acceptable before the vendors are awarded contracts. The acceptance of the vendor's QA program is based on a review of the vendor's QA program manual/procedures and the performance of an on-site facility QA audit. For the SHNPP project, manual reviews and facility audits are performed by CP&L Vendor Surveillance Unit, Ebasco and/or Westinghouse personnel. During a facility QA audit conducted by CP&L Vendor Surveillance Unit personnel, a prepared checklist is used which included questions concerning verification of design adequacy and design analysis.
After a contract has been awarded, CP&L Vendor Surveillance Specialists perform shop inspections at the vendor's facilities to verify that the requirements of the specification for Class 1E electrical components are being met. During these surveillance visits, the Vendor Surveillance Specialists verify that a report is available for components that require environmental qualification. The CP&L Vendor Surveillance Specialists verify that the report represents the equipment that is being purchased and that the report has been approved by authorized laboratory, vendor, and CP&L personnel.
Ebasco and Westinghouse surveillance 'representatives also perform shop inspections for contracts for which they are responsible. These surveillance representatives verify that electrical component qualification reports are available and that the reports have been approved by authorized laboratory, vendor and Ebasco/Westinghouse personnel.
As part of the equipment qualification program, a review is done of the results of any testing. If, during this review, anomalies, gaps in testing, sample description discrepancies or improper assumptions are noted, the vendor is contacted. In some instances, visits to the vendors shops by Equipment Qualification Engineers have been made to personally verify the information and inspect the tested equipment. Additionally, comparison qualification (i-e., qualification by comparison to a similar tested component) is given a careful review to assure proper logic and basis.
Item 2, p. 5 of the Sandia report which is referenced in the contention was addressed by the Staff in the "Discussion of Sandia Items" attached to the memorandum from William J. Dircks to the Commissioners, dated February 2, 1984. Item 2 is-discussed together with certain other items. There are several inspection reports listed with those items. A review of those reports shows that Item 2 is taken from Inspection Report No. 9990277/83-02, which documents the results of an inspection of The Rockbestos Company conducted on June 20-23 and August 16-17, 1983.
10 (401PSA/ccc)
The Inspection Report (p. 10, ll, and 14) questions the use of the company 's qualification test report f/2806 to qualify their entire 100 series line of cable, particularly in view of the fact that in the same test used to qualify RSS-6-104 type cables, four other type cables in the 100 series line failed the test.
The Rockbestos cable company uses their qualification test report //2806, which describes LOCA testing on R85-6-104 cable, to assert the qualification of their entire 100 series line. No mention is made of the RSS-6-100A, RSS-6-109, RSS-6-110, RSS-6-112 which were also a part of the qualification test used to generate QR2806 and failed.
Shearon Harris uses the RSB-6-104, RSS-6-105 and RSS-6-108 type cables. The RSS-6-104 was the model actually tested and did pass the test. RSS-6-105 and RSS-6-108 are used in the electrical containment penetrations only. A review of the spec sheets for these two models and discussions with Rockbestos have shown that the two cable types are very well represented, by comparison, to the RSS-6-104 alone. This comparison uses cable specifications such as installation material and thickness, and jacket material and thickness as comparison variables. As can-be seen by the attached equipment manufacturing catalog sheets, cable types RSS-6-104 and RSS-6-105 differ only in minor differences in the insulation material. Rockbestos has stated that the RSS-6-105 insulation is a higher quality insulation type than the RSS-6-104 which was successfully tested. The major differences between RSS-6-108 and the tested RSS-6-104 are that the 108 cable is a triaxial cable while the 104 cable is a coaxial cable, and the 108 cable contains the higher quality insulation similar to the 105 cable. Additionally, for the first jacket of the RSS-6-108 cable, it can be noted that the insulation/shielding/jacketing subsequently has a second thick is greater than the RSS-6-104. The RSS-6-108 shield and second jacket. Any comparisons done to establish qualifications are documented in the equipment qualification documentation packages.
Therefore, the 2806 report can be used to qualify all three types of Rockbestos cable at Shearon Harris.
Shearon Harris does not use any of the type cables which failed during the qualification program used to generate QR2806.
11 (401PSA/ccc)
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RSS-6-108/LE Date << 3/15/83 Tr faxfal Cable - Low Noise Adverse Servfce Revision - 0
.460 + .009 .400 .370 .315 .285 + enn7 .064 .n48 I
2nd Jacket 2nd Shield 1st Jacket 1st Shield 2nd Insulation 1st Insulation Conductor Descrfptfon Construction Details Conductor 18 AtG Tin Coated Copper (7x26) to ASTH 833 5 B286 1st Insulation Roclbestos Polvmer LE 2nd Insulatf on Radiatior. Cross-Linked, Low Noise Treated, Hodf fied Polyoleffn 1st Shield 33 Q4 Tin '.ed Copper to ASllf 833, 9N (mfnfnum) coverage 1st Jacket Radiation Cross-Linked Fla Retardan Non-Corrosive Modified Pol oleffn 2nd Shield 33 AV"= Tin Coated Copper to ASTH 833, 90K (minimum) Coverage 2nd Jacket Radiation Cross-Linked, Flame Retardant, Non-Corrosive Modified Polydleffn Flectrtca~tPre erttee Impedance 72 ohms (nomfnal)
Caoac f tance 21.7 nf/ft. (nominal) For Fnnfneerfnn Velocity 65". (nominal) oefnrence nnlv Dfelectr fc Constant 2.3 (nomfnal)
<<Corona Extinction 10n0 volts (rms} (minimum)
<<Insulatfon Sesfstance 106 megohms for 1000 ft. (mfnfnxim)
<<Dielectric llftlstand 5000 volts (rms) (mfnfnxnn) lqng volts (rms) (mfnfrmm) bellmen s~felds Physical Pro rties Me aht
'l; 140 lh/1000 ft. (nominal)
Ilfnimum Bend Fa Ee5 inches for oermanent installation Environmental Pronertfes Cold Bend -4"'C on a 4.75 inch mandrel Flamnabf1 f ty <<IorEA S-19-81, Sec. 6.19.6 (September 1977)
This cable fs suitable for C'lass 1K service fn nuclear generating stations and meets annlfcahle renufrements of lEEE 383-1974. Unless otherwfse specified, printed legend will include "Rockbestos RSS-6-108/LE. 19XX."
Dimensions are fn inches and are nor'.nal unless othen!fse desfqnated.
Required tests to be run fn accordance i ith "ockbestns Test procedures.
- Production Tests T'IXK ~DCWK3Ke I OR <OWXFWi~~
NEW HAVEN, CONNECTICUT 06504 USA TELEPHONE: (203) 772-2250 TELEX: 710-465-2149
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RSS-6'-105/L f Date - 3/15/83 Cassia! ra!1 e - Loe !!atae Adverse Service Revisfon 0
.242 + .004 .173 .146 + .n04 .048 e032 Jacket Shield 2nd Insulation 1st Insulation Conductor Description Construction Details Conductor 22 "'". Tin Coated Copper (lgx34) to ASTi'33 A 8286 1st Insulation Rocgestos Polymer LE 2nd Insulation tladfatfon Cross-Linked, Low ~tofse Treated, tiodfffed Polyoleffn Shield 34 PiRG Tin Coated Conper to ASTli 833, 90".. (Nnfmum) Coverage Jacket P~diatfon Cross-Linked, Flame Retardant, Von-Corrosive 'hdflfed Polyoleffn Electrical Pro ertfes Impedance 62 ohns (nominal)
Capacitance ?5.7 pf/ft. nominal) For Fnqineerfnn Velocity 64 (nominal Reference denly Dielectric Constant 2.4 (nominal
- Corona'Extinction 23PO volts (rms) (mini
- Insulation Resistance 1C~ megohms for lfi00 ft. ( minimum)
<<Dielectric Mfthstand 500" volts (rms) (mfnfmsm Oar~a!col pro erases Me(I ght 36.6 lb/1000 ft. (nominal) ilfnfmum Bend Radius 3.0 inches for permanent installation Cold Bend -4n'C on a 2.5 fnch mandrel Flaiunabflfty <<IPCEP. 5-10-8'I, .ec. E.l 8.6 (Seotemher 1977)
This cable fs suitable ~or rla~s lr service in nuclear neneratfno stations and meets annlfcahie rec.ufrements" of 1EEE 383-1874. Unless otherwise specified, printed legend will include "Rockbestos RSS-6-105/Lfe lgXX Dimensions are fn inches and are nominal unless otherwise desfonated.
Reoufred Tests to be run ir a" or".ace rftii Rockbestos Test Procedures.
<<Production Tests T'&K AOCIZHKB1 OR C'OMX WN Y NEW HAVEN, CONNECTICUT06504 USA TELEPHONE: (203) 772-2250 TELEX: 710465-2149
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t RSS-6-104 Date - 1/20/78 Coaxial .Ci-bl e Adverse Servi n n-
.242 + .004 .173 .146 + .004 .048 .032 Jacket Shield 2nd Insulation 1st insulation Conductor Descrintion Constr c Corductor 22 A'iG Tin Coated Co oer lgx34 to AS'33 5 8286 1st Insulation Rockbestos Polymer LD 2nd Insulation Radiation Cross-Linked modified Pol 1efin Shield 34 AMG Tin Coated Cooper to ASTH 833, 90. (!minimum) Coveraoe Jacket Radiation Cross-Linked. Flame Retardant. !Ion-Corrosive tiodified Polyolefin Impedance (nominal ) )
Capacitance 25.7 nf/ft. nominal) For Enqineer'inq Velocity 64" (nominal Peference denly Dielectric Constant 2.4 (nominal
~ Corona Extinction 23/0 volts (rms) {nominal)
<<Insulation Resistance
~ Dielectric Mithstand 10'eqohms for 1000 ft. (minimum) 5000 volts (rms) (minimum Meight 36.6 lb/1000 Ft. {nominal)
Minimum Bend Radius 3.0 inches for nermanent installation Environmental Pro erties Cold Bend -40'C on a 2.5 inch mandrel Flaamability ~ IPCEA 5-19-81, Dec. 6.19.6 (Septemher 1977)
This cable is suitable for Class lE service in nuclear generating stations and meets annlicable reouirements of 1EEE 383-1974. The cable wi11 operate at temperatures up to 250'C for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 171'C for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and 150'C for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Continuous service uo to 110'C; Dimensions are in inches and are nominal unless othentise desionated.
Pequired tests to he run in accordance uith Rockbestos Test Procedures.
<<Production Tests 5 HE EC()VIi'V NEW HAVEN, CONNECTICUT 06504 USA TELEPHONE: (203) 772-2250 TELEX: 710-465-2149
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